Uranium Enrichment Reduction in the Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) with PBO Reflector

Kim, Chihyung; Hartanto, Donny; Kim, Yong Hee

doi:10.1016/j.net.2016.01.005

Cited by 11 publications

(3 citation statements)

References 3 publications

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“…ere are seven control element assemblies in the core, and they are divided into four primary and three secondary control assembly groups. A relatively thick PbO reflector (3 rings or 126 reflector assemblies) improves the neutron reflection performance [12]. A ring of shield assemblies surrounds the core.…”

Section: Bandbr Designmentioning

confidence: 99%

Study on the Sensitivity and Uncertainty of Nuclear Data to the Sodium-Cooled Linear Breed-and-Burn Fast Reactor Using SCALE6.2 Code

Hartanto

2021

Science and Technology of Nuclear Installations

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Previously, the neutronics design of a small and compact linear breed-and-burn fast reactor (B&BR) was completed. The reactor produces 400 MWth power, and it can operate with excess reactivity of less than 1$ for more than 50 years without refuelling. As the blanket fuel, the spent nuclear fuel (SNF) from existing light water reactors (LWRs) is used to reduce the burden from the problematic long-lived isotopes in SNF. However, by loading massive nuclides at the initial core, the impact of nuclear data uncertainty on the reactivity calculation results of SNF-fuelled B&BR at the beginning of life (BOL) is expected to be significant because these nuclides have different credentials in evaluated nuclear data libraries. In this study, the impact of nuclear library uncertainty from ENDF/B-VII.0 and ENDF/B-VII.1 on reactivity calculation of B&BR is evaluated using the continuous-energy TSUNAMI-3D module in the SCALE6.2 code package. The uncertainty of reactivity calculation results of B&BR caused by the inaccuracy of two libraries is significant (more than 2000 pcm), mainly from the uncertainty of 235,238U and 56Fe cross section. The energy-dependent sensitivity profiles show that they are significant at the fast energy range. The uncertainty of coolant void reactivity (CVR) is about 18%, and that of fuel temperature coefficient (FTC) is about 15% of the reactivity effect. The top five contributions for CVR accounted for elastic scattering of 238U, capture of 235,238U, and elastic scattering of 23Na and 56Fe. Meanwhile, the top contributors for FTC were accounted for elastic scattering of 238U and 56Fe, capture of 235U, and elastic scattering of 94Zr and 57Fe. It is highly recommended to improve the accuracy of those isotopes’ cross sections at the high energy range to provide a more reliable reactivity calculation for the fast system.

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Section: Bandbr Designmentioning

confidence: 99%

Study on the Sensitivity and Uncertainty of Nuclear Data to the Sodium-Cooled Linear Breed-and-Burn Fast Reactor Using SCALE6.2 Code

Hartanto

2021

Science and Technology of Nuclear Installations

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“…A prototype Gen IV sodium‐cooled fast reactor (PGSFR) is being developed in combination with the pyro‐electrochemical processing of spent fuel at KAERI . It can resolve the issue of the accumulation of PWR (pressurized water reactor) spent fuels and can increase the utilization of uranium resources while maintaining higher proliferation resistance .…”

Section: Introductionmentioning

confidence: 99%

Ceramic plasma‐spray‐coated graphite crucible for injection casting of fast reactor fuel slugs

Kim

Hong

Kim

et al. 2018

Int J Applied Ceramic Tech

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Ceramic plasma-spray coatings with single and multiple layers have been applied to melting crucible material substrates for the development of a reusable crucible for the fabrication of metal fuel slugs for a sodium-cooled fast reactor (SFR). Various combinations of vacuum plasma-spray (VPS) coated specimens have been applied to investigate the bonding effect on the crucible substrate and the interaction between the metal fuel and the VPS-coated crucible substrate. All VPS-coated methods maintained a sound coating state after a dipping test with U-10 wt%Zr melt. A single coating of a Y 2 O 3 (150) layer and a double coating layer of TaC(50)-Y 2 O 3 (100) showed some degradation or penetration, respectively, after 2 cycles of dipping test with an aggressive U-10 wt%Zr-5 wt%RE melt. Injection castings of U-10 wt%Zr and U-10 wt%Zr-5 wt%RE fuel slugs were also conducted to investigate the feasibility of a reusable melting crucible of metal fuel slugs. The U-10 wt% Zr fuel slugs were soundly fabricated without significant interactions of the graphite crucibles; however, the U-10 wt%Zr-5 wt%RE fuel slugs had some degradation or penetration, respectively, after injection casting. K E Y W O R D Sinjection casting, interaction, melting crucible, metal fuel, vacuum plasma-spray

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“…KAERI seeks to develop and demonstrate the technologies needed to transmute the long-lived transuranic actinide isotopes in spent nuclear fuel into shorter-lived fission products, thereby dramatically decreasing the material volume requiring disposal, the long-term radiotoxicity, and the heat load of high-level waste sent to a geological repository [1,2]. A prototype Gen IV sodium-cooled fast reactor (PGSFR) is being developed in combination with the pyroelectrochemical processing of spent fuel in KAERI [3]. It can solve the problem of the accumulation of pressurized water reactor (PWR) spent fuel and can increase the utilization of uranium resources while maintaining a higher proliferation resistance.…”

Section: Introductionmentioning

confidence: 99%

Fabrication of U-10 wt.%Zr Metallic Fuel Rodlets for Irradiation Test in BOR-60 Fast Reactor

Kim

et al. 2016

Science and Technology of Nuclear Installations

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The fabrication technology for metallic fuel has been developed to produce the driver fuel in a PGSFR in Korea since 2007. In order to evaluate the irradiation integrity and validate the in-reactor of the starting metallic fuel with FMS cladding for the loading of the metallic fuel, U-10 wt.%Zr fuel rodlets were fabricated and evaluated for a verification of the starting driver fuel through an irradiation test in the BOR-60 fast reactor. The injection casting method was applied to U-10 wt.%Zr fuel slugs with a diameter of 5.5 mm. Consequently, fuel slugs per melting batch without casting defects were fabricated through the development of advanced casting technology and evaluation tests. The optimal GTAW welding conditions were also established through a number of experiments. In addition, a qualification test was carried out to prove the weld quality of the end plug welding of the metallic fuel rodlets. The wire wrapping of metallic fuel rodlets was successfully accomplished for the irradiation test. Thus, PGSFR fuel rodlets have been soundly fabricated for the irradiation test in a BOR-60 fast reactor.

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Uranium Enrichment Reduction in the Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) with PBO Reflector

Cited by 11 publications

References 3 publications

Study on the Sensitivity and Uncertainty of Nuclear Data to the Sodium-Cooled Linear Breed-and-Burn Fast Reactor Using SCALE6.2 Code

Study on the Sensitivity and Uncertainty of Nuclear Data to the Sodium-Cooled Linear Breed-and-Burn Fast Reactor Using SCALE6.2 Code

Ceramic plasma‐spray‐coated graphite crucible for injection casting of fast reactor fuel slugs

Fabrication of U-10 wt.%Zr Metallic Fuel Rodlets for Irradiation Test in BOR-60 Fast Reactor

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